BENCHMARKING OF THE 3D CFD CODE GASFLOW II WITH CONTAINMENT THERMAL HYDRAULIC TESTS FROM HDR AND THAI
BENCHMARKING OF THE 3D CFD CODE GASFLOW II WITH CONTAINMENT THERMAL HYDRAULIC TESTS FROM HDR AND THAI
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发表时间：
2006
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通讯作者：
P. Royl;U. Lee;J. Travis;W. Breitung;Forschungszentrum Karlsruhe
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作者：
P. Royl;U. Lee;J. Travis;W. Breitung;Forschungszentrum Karlsruhe
对核反应堆安全壳内蒸汽-氢气释放所产生的热工水力条件有很好的了解，是事故管理和缓解措施设计的所有方面所必需的。GASFLOW II代码是在卡尔斯鲁厄研究中心（FZK）开发的，用于分析此类情况。它解决了三维可压缩瞬态Navier-Stokes方程。本文将报告GASFLOW II的新验证，其中包括在新的ThAI遏制测试设施和德国的Heissdampfreaktor（HDR）中模拟此类条件的盲态和开放式测试后模拟实验。
A good understanding of the thermal hydraulic conditions resulting from steam-hydrogen releases in nuclear reactor containments is required for all aspects of accident management and for the design of mitigation measures. The GASFLOW II code has been developed at Forschungszentrum Karlsruhe (FZK) for analysis of such scenarios. It solves the three dimensional compressible transient Navier Stokes equations. This contribution will report on new validations of GASFLOW II with blind and open post-test simulations of experiments that simulate such conditions in the new ThAI containment test facility and in the Heissdampfreaktor (HDR) in Germany.